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Title: Nuclear data needs for advanced reactor systems. A NEA nuclear science committee initiative.

Abstract

The Working Party on Evaluation Cooperation (WPEC) of the OECD Nuclear Energy Agency Nuclear Science Committee has established an International Subgroup to perform an activity in order to develop a systematic approach to define data needs for Gen-IV and, in general, for advanced reactor systems. A methodology, based on sensitivity analysis has been agreed and representative core configurations for Sodium, Gas and Lead cooled Fast Reactors (SFR, GFR, LFR) have been defined as well as a high burn-up VHTR and a high burn-up PWR. In the case of SFRs, both a TRU burner (called in fact SFR) and a core configuration with homogeneous recycling of not separated TRU (called EFR) have been considered. The methodology, the systems considered and the sensitivity approach are consistent with the work reported in ref. [1]. For the present study, the approach has been extended to the ABTR Na-cooled core, recently studied within the GNEP initiative [2]. Sensitivity coefficients (in a 15 energy group structure) have been calculated at ANL with the ERANOS code system [3] for all reactors and for the parameters most sensitive to nuclear data uncertainties: Multiplication factor, Power peak, Burn-up {Delta}k/k, Coolant void reactivity coefficient, Doppler reactivity coefficient, Nuclide density atmore » end of cycle (transmutation potential), Neutron source at fuel fabrication, Dose in a repository.« less

Authors:
; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ; ;
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
Sponsoring Org.:
USDOE Office of Science (SC)
OSTI Identifier:
977025
Report Number(s):
ANL/NE/CP-59059
TRN: US1002757
DOE Contract Number:
DE-AC02-06CH11357
Resource Type:
Conference
Resource Relation:
Conference: 2007 International Conference on Nuclear Data for Science and Technology (ND2007); Apr. 22, 2007 - Apr. 27, 2007; Nice, France
Country of Publication:
United States
Language:
ENGLISH
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; BURNERS; CONFIGURATION; COOLANTS; FABRICATION; FAST REACTORS; ISOTOPES; MULTIPLICATION FACTORS; NEA; NEUTRON SOURCES; OECD; REACTIVITY COEFFICIENTS; RECYCLING; SENSITIVITY; SENSITIVITY ANALYSIS; SODIUM; TRANSMUTATION

Citation Formats

Salvatores, M., Aliberti, G., Palmiotti, G., Rochman, D., Oblozinsky, P., Hermann, M., Talou, P., Kawano, T., Leal, L., Koning, A., Kodeli, I., Nuclear Engineering Division, CEA Cadarache, BNL, LANL, ORNL, NRG-Petten, and NEA-Databank. Nuclear data needs for advanced reactor systems. A NEA nuclear science committee initiative.. United States: N. p., 2008. Web.
Salvatores, M., Aliberti, G., Palmiotti, G., Rochman, D., Oblozinsky, P., Hermann, M., Talou, P., Kawano, T., Leal, L., Koning, A., Kodeli, I., Nuclear Engineering Division, CEA Cadarache, BNL, LANL, ORNL, NRG-Petten, & NEA-Databank. Nuclear data needs for advanced reactor systems. A NEA nuclear science committee initiative.. United States.
Salvatores, M., Aliberti, G., Palmiotti, G., Rochman, D., Oblozinsky, P., Hermann, M., Talou, P., Kawano, T., Leal, L., Koning, A., Kodeli, I., Nuclear Engineering Division, CEA Cadarache, BNL, LANL, ORNL, NRG-Petten, and NEA-Databank. 2008. "Nuclear data needs for advanced reactor systems. A NEA nuclear science committee initiative.". United States. doi:.
@article{osti_977025,
title = {Nuclear data needs for advanced reactor systems. A NEA nuclear science committee initiative.},
author = {Salvatores, M. and Aliberti, G. and Palmiotti, G. and Rochman, D. and Oblozinsky, P. and Hermann, M. and Talou, P. and Kawano, T. and Leal, L. and Koning, A. and Kodeli, I. and Nuclear Engineering Division and CEA Cadarache and BNL and LANL and ORNL and NRG-Petten and NEA-Databank},
abstractNote = {The Working Party on Evaluation Cooperation (WPEC) of the OECD Nuclear Energy Agency Nuclear Science Committee has established an International Subgroup to perform an activity in order to develop a systematic approach to define data needs for Gen-IV and, in general, for advanced reactor systems. A methodology, based on sensitivity analysis has been agreed and representative core configurations for Sodium, Gas and Lead cooled Fast Reactors (SFR, GFR, LFR) have been defined as well as a high burn-up VHTR and a high burn-up PWR. In the case of SFRs, both a TRU burner (called in fact SFR) and a core configuration with homogeneous recycling of not separated TRU (called EFR) have been considered. The methodology, the systems considered and the sensitivity approach are consistent with the work reported in ref. [1]. For the present study, the approach has been extended to the ABTR Na-cooled core, recently studied within the GNEP initiative [2]. Sensitivity coefficients (in a 15 energy group structure) have been calculated at ANL with the ERANOS code system [3] for all reactors and for the parameters most sensitive to nuclear data uncertainties: Multiplication factor, Power peak, Burn-up {Delta}k/k, Coolant void reactivity coefficient, Doppler reactivity coefficient, Nuclide density at end of cycle (transmutation potential), Neutron source at fuel fabrication, Dose in a repository.},
doi = {},
journal = {},
number = ,
volume = ,
place = {United States},
year = 2008,
month = 1
}

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  • The Working Party on Evaluation Cooperation (WPEC) of the OECD Nuclear Energy Agency Nuclear Science Committee has established an International Subgroup to perform an activity in order to develop a systematic approach to define data needs for Gen-IV and, in general, for advanced reactor systems. A methodology, based on sensitivity analysis has been agreed and representative core configurations for Sodium, Gas and Lead cooled Fast Reactors (SFR, GFR, LFR) have been defined as well as a high burn-up VHTR and a high burn-up PWR. In the case of SFRs, both a TRU burner (called in fact SFR) and a coremore » configuration with homogeneous recycling of not separated TRU (called EFR) have been considered.« less
  • On July 20, 1989, the President of the United States announced a new direction for the US Space Program. The new Space Exploration Initiative (SEI) is intended to emplace a permanent base on the Lunar surface and a manned outpost on the Mars surface by 2019. In order to achieve this ambitious challenge, new, innovative and robust technologies will have to be developed to support crew operations. Nuclear power and propulsion have been recognized as technologies that are at least mission enhancing and, in some scenarios, mission enabling. Because of the extreme operating conditions present in a nuclear rocket core,more » accurate modeling of the rocket will require cross section data sets which do not currently exist. In order to successfully achieve the goals of the SEI, major obstacles inherent in long duration space travel will have to be overcome. One of these obstacles is the radiation environment to which the astronauts will be exposed. In general, an unshielded crew will be exposed to roughly one REM per week in free space. For missions to Mars, the total dose could exceed more than one-half the total allowed lifetime level. Shielding of the crew may be possible, but accurate assessments of shield composition and thickness are critical if shield masses are to be kept at acceptable levels. In addition, the entire ship design may be altered by the differential neutron production by heavy ions (Galactic Cosmic Rays) incident on ship structures. The components of the radiation environment, current modeling capability and envisioned experiments will be discussed.« less
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  • A target accuracy assessment study using both a fine and a broad energy structure has shown that less stringent nuclear data accuracy requirements are needed for the latter energy structure. However, even though a reduction is observed, still the requirements will be very difficult to be met unless integral experiments are also used to reduce nuclear data uncertainties. Target accuracy assessment is the inverse problem of the uncertainty evaluation. To establish priorities and target accuracies on data uncertainty reduction, a formal approach can be adopted by defining target accuracy on design parameters and finding out required accuracy on data inmore » order to meet them. In fact, the unknown uncertainty data requirements can be obtained by solving a minimization problem where the sensitivity coefficients in conjunction with the constraints on the integral parameters provide the needed quantities for finding the solutions.« less
  • At the occasion of the restructurisation of the Committees at the Nuclear Energy Agency (OECD, Paris), the newly formed Nuclear Energy Agency Nuclear Science Committee (NEA-NSC) took over some of the activities of the former Nuclear Energy Agency Nuclear Data Committee (NEA-NDC). Amongst these activities were two Interlaboratory Collaborations, one on an important standard, the {sup 10}B(n,{alpha}) cross-section, the other on measurements of activation cross-sections. Progress of these two NEA-NSC Interlaboratory Collaborations is reported.